Browse "NE-Journal Papers(저널논문)" by Author No, Hee-Cheon
Showing results 1 to 47 of 47
| A 9-Rule Fuzzy Logic Controller of the Nuclear Steam Generator Lee, Jae-Young; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.25, no.3, pp.371 - 380, 1993-01 |
| A simple model for the quench front propagation in a highly superheated particle bed Yeo, D. Y.; No, Hee-Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.136, pp.644 - 654, 2019-06 |
| A zero-dimensional dryout heat flux model based on mechanistic interfacial friction models for two-phase flow regimes with channel flow in a packed bed Yeo, DY; No, Hee-Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.141, pp.554 - 568, 2019-10 |
| An intermediate heat exchanging-depressurizing loop for nuclear hydrogen production Kim, Young-Soo; No, Hee-Cheon; Yoon, Ho-Joon; Lee, Jeong-Ik, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.2957 - 2962, 2010-10 |
| Assessment of Two Wall Film Condensation Models of RELAP5/MOD3.2 in the presence of Noncondensable Gas in a Vertical Tube Park, Hyun-Sik; No, Hee-Cheon; Bang, Young-Seok, NUCLEAR ENGINEERING AND TECHNOLOGY, v.31, no.5, pp.465 - 475, 1999-01 |
| Boric Acid Concentration in the Core during the Long Term Cooling Phase of Pressurized Water Reactors Kim, Chang-Hyun; Kim, Young-Soo; Jun, Hwang-Young; No, Hee-Cheon, ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, v.58, no.2, pp.88 - 94, 2013-02 |
| Bubble Lift-off Diameter and Nucleation Frequency in Vertical Subcooled Boiling Flow Chu, In-Cheol; No, Hee-Cheon; Song, Chul-Hwa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.48, no.6, pp.936 - 949, 2011-06 |
| CFD-assisted scaling methodology and thermal-hydraulic experiment for a single spent fuel assembly Yoo, Seung-Hun; No, Hee-Cheon; Kim, Hyeun-Min; Lee, Eo-Hwak, NUCLEAR ENGINEERING AND DESIGN, v.240, no.12, pp.4008 - 4020, 2010-12 |
| Demonstration of the I-S thermochemical cycle feasibility by experimentally validating the over-azeotropic condition in the hydroiodic acid phase of the Bunsen process Yoon, Ho-Joon; No, Hee-Cheon; Kim, Young-Soo; Jin, Hyung-Gon; Lee, Jeong-Ik; Lee, Byung-Jin, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.34, no.19, pp.7939 - 7948, 2009-10 |
| Design optimization of multi-layer Silicon Carbide cladding for light water reactors Lee, Youho; No, Hee-Cheon; Lee, Jeong Ik, NUCLEAR ENGINEERING AND DESIGN, v.311, pp.213 - 223, 2017-01 |
| Development of a critical heat flux mapping method for fin-structured surfaces Choi, Jin Young; No, Hee-Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.9, pp.1321 - 1331, 2016 |
| Development of a dry patch model for critical heat flux prediction Choi, Jin Young; No, Hee-Cheon; Kim, Jegon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.100, pp.386 - 395, 2016-09 |
| Development of a flowsheet for iodine-sulfur thermo-chemical cycle based on optimized Bunsen reaction Lee, Byung-Jin; No, Hee-Cheon; Yoon, Ho-Joon; Jin, Hyung-Gon; Kim, Young-Soo; Lee, Jeong-Ik, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.34, no.5, pp.2133 - 2143, 2009-03 |
| Development of a semi -empirical model -based COrium COolability analysis tool (COCOA) validated against a large scale corium experiment, FARO Kim, Jaeha; Yoon, S. H.; Song, Mun Won; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.364, 2020-08 |
| Development of scaling laws of heat removal and CFD assessment in concrete cask air path Kim, Hyeun Min; No, Hee-Cheon; Bang, Kyoung Sik; Seo, Ki Seog; Lee, Sang Hoon, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.7 - 16, 2014-10 |
| Effects of the onset time of natural circulation on safety in an air ingress accident involving a HTGR Jin, Hyung-Gon; No, Hee-Cheon; Park, Byung-Ha, NUCLEAR ENGINEERING AND DESIGN, v.250, pp.626 - 632, 2012-09 |
| Experimental benchmarks and simulation of GAMMA-T for overcooling and undercooling transients in HTGRs coupled with MED desalination plants Kim, Ho-Sik; Kim, In-Hun; No, Hee-Cheon; Jin, Hyung-Gon, NUCLEAR ENGINEERING AND DESIGN, v.259, pp.29 - 40, 2013-06 |
| Experimental study for pressure drop and flow instability of two-phase flow in the PCHE-type steam generator for SMRs Shin, Chang Wook; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.318, pp.109 - 118, 2017-07 |
| Failure probabilities of SiC clad fuel during a LOCA in public acceptable simple SMR (PASS) Lee, Youho; Kim, Ho Sik; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.292, pp.1 - 16, 2015-10 |
| FEASIBILITY STUDY OF A DEDICATED NUCLEAR DESALINATION SYSTEM: LOW-PRESSURE INHERENT HEAT SINK NUCLEAR DESALINATION PLANT (LIND) Kim, Ho Sik; No, Hee-Cheon; Jo, Yugwon; Wibisono, Andhika Feri; Park, Byung Ha; Choi, Jinyoung; Lee, Jeong-Ik; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.3, pp.293 - 305, 2015-04 |
| Freezing technique for measuring and predicting the size of droplets in a horizontal annular flow Lee, Eo-Hwak; No, Hee-Cheon; Yoo, Seung-Hun; Lee, Kyung-Won; Song, Chul-Hwa, NUCLEAR ENGINEERING AND DESIGN, v.240, no.7, pp.1795 - 1802, 2010-07 |
| Full-scope simulation of a dry storage cask using computational fluid dynamics Yoo, Seung-Hun; No, Hee-Cheon; Kim, Hyeun-Min; Lee, Eo-Hwak, NUCLEAR ENGINEERING AND DESIGN, v.240, no.12, pp.4111 - 4122, 2010-12 |
| Impacts of transient heat transfer modeling on prediction of advanced cladding fracture during LWR LBLOCA Lee, Youho; Lee, Jeong-Ik; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.298, pp.25 - 32, 2016-03 |
| Improvement of the reflood model of RELAP5/MOD3.3 based on the assessments against FLECHT-SEASET tests Choi, Tong-Soo; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.240, no.4, pp.832 - 841, 2010-04 |
| Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity Lee, Youho; Kim, Bokyung; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.307, pp.402 - 410, 2016-10 |
| Interfacial Wave Characteristics for Countercurrent Stratified Air-Water Flow in a Horizontal Pipe Chung, Heung-June; Chun, Se-Young; Chung, Moon-Ki; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.28, no.4, pp.379 - 389, 1996-08 |
| KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA No, Hee-Cheon; Ha, Sang-Jun; Kim, Kyung-Doo; Lim, Hong-Sik; Lee, Eo-Hwak; Jin, Hyung-Gon, NUCLEAR TECHNOLOGY, v.181, no.1, pp.24 - 43, 2013-01 |
| Local Heat Transfer Coefficients for Reflux Condensation Experiment in a Vertical Tube in the Presence of Noncondensible Gas Moon, Young-Min; No, Hee-Cheon; Bang, Young-Seok, NUCLEAR ENGINEERING AND TECHNOLOGY , v.31, no.5, pp.486 - 497, 1999-01 |
| Methodology of CFD analysis for evaluating H-2 explosion accidents in an open space Kang, Hyung Seok; No, Hee-Cheon; Kim, Sang Baik; Kim, Min Hwan, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.40, no.7, pp.3075 - 3090, 2015-02 |
| Model development for fragment-size distribution based on upper-limit log-normal distribution Kim, Jegon; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.349, pp.86 - 91, 2019-08 |
| Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling Yeo, D. Y.; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.342, pp.219 - 230, 2019-02 |
| Modeling film boiling within chimney-structured porous media and heat pipes Yeo, D. Y.; No, Hee-Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.124, pp.576 - 585, 2018-09 |
| Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors Yeo, Dongyeol; No, Hee-Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.108, pp.868 - 879, 2017-05 |
| Modeling of high pressure steam condensation in inclined horizontal tubes of PAFS in APR Yun, Bong Yo; No, Hee-Cheon; Shin, Chang Wook, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.9, pp.1353 - 1365, 2016 |
| Multi-tube effect of external condensation with non-condensable gas in a tube bundle Kim, Do Yun; No, Hee-Cheon; Jeon, Byong Guk; Lim, Sang Gyu; Yoon, Ho Joon, ANNALS OF NUCLEAR ENERGY, v.168, 2022-04 |
| Neutron Noise Analysis for PWR Core Motion Monitoring Yun, Won-Young; Koh, Byung-Jun; Park, In-Yong; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.20, no.4, pp.253 - 264, 1988-12 |
| Observation of critical heat flux mechanism in horizontal pool boiling of saturated water Chu, In-Cheol; No, Hee-Cheon; Song, Chul-Hwa; Euh, Dong Jin, NUCLEAR ENGINEERING AND DESIGN, v.279, pp.189 - 199, 2014-11 |
| Physical model development and optimal design of PCHE for intermediate heat exchangers in HTGRs Kim, In-Hun; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.243, pp.243 - 250, 2012-02 |
| Stability and kinetics of powder-type and pellet-type iron (III) oxide catalysts for sulfuric acid decomposition in practical Iodine-Sulfur cycle Kim, Young-Soo; No, Hee-Cheon; Choi, Jin-Young; Yoon, Ho-Joon, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.38, no.9, pp.3537 - 3544, 2013-03 |
| STATUS AND PLAN OF THE SYSTEM CODES DEVELOPMENT FOR ITER TEST BLANKET MODULE AND FUSION BREEDING BLANKET IN KOREA Lee, Dong-Won; Yum, Soo-Been; Park, Goon-Cherl; Kim, Seol-Ha; Kim, Moo-Hwan; Jin, Hyung-Gon; No, Hee-Cheon; et al, FUSION SCIENCE AND TECHNOLOGY, v.64, no.3, pp.645 - 650, 2013-09 |
| Stratified flow-induced air-ingress accident assessment of the GAMMA code in HTGRs Jin, Hyung-Gon; No, Hee-Cheon; Kim, Hyeon-Il, NUCLEAR ENGINEERING AND DESIGN, v.241, no.8, pp.3216 - 3223, 2011-08 |
| Thermal hydraulic performance analysis of a printed circuit heat exchanger using a helium-water test loop and numerical simulations Kim, In-Hun; No, Hee-Cheon, APPLIED THERMAL ENGINEERING, v.31, no.17-18, pp.4064 - 4073, 2011-12 |
| Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations Kim, In-Hun; No, Hee-Cheon; Lee, Jeong-Ik; Jeon, Yong-Guk, NUCLEAR ENGINEERING AND DESIGN, v.239, no.11, pp.2399 - 2408, 2009-11 |
| Thermal-hydraulic evaluation of passive containment cooling system of improved APR plus during LOCAs Jeon, Byong Guk; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.190 - 198, 2014-10 |
| Thermal-hydraulic physical models for a Printed Circuit Heat Exchanger covering He, He-CO2 mixture, and water fluids using experimental data and CFD Kim, In-Hun; No, Hee-Cheon, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.48, pp.213 - 221, 2013-07 |
| Transient Multicomponent Mixture Analysis Based on an ICE Numerical Technique for the Simulation of an Air Ingress Accident in an HTGR Lim, Hong-Sik; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.36, no.5, pp.375 - 387, 2004-10 |
| Transient Multicomponent Mixture Analysis Based on an ICE Numerical Technique for the Simulation of an Air Ingress Accident in an HTGR Lim, Hong Sik; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.36, no.5, pp.375 - 387, 2004-10 |
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